ML20138F397

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Myap Annual Radioactive Effluent Release Rept Jan-Dec 1996
ML20138F397
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Site: Maine Yankee
Issue date: 12/31/1996
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Maine Yankee
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ML20138F392 List:
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NUDOCS 9705050384
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Text

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MAINE YANKEE ATOMIC POWER COMPANY ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January-December 1996

1.0 INTRODUCTION

Tables 1 and 2 summarize the quantity of radioactive gaseous and liquid effluents, respectively, for each quarter of 1996. Table 3 summarizes the solid waste shipped off-site for burial or disposal during 1996. Table 4 contains supplementary information.

Appendices A through D indicate the status of reportable items per the requirements of ODCM sections 2.1.5,2.2.6,2.3.3,2.3.4,2.5 and Appendix C.

Changes to the ODCM during 1996 included minor editorial changes to several pages, and incorporation of a site boundary map at Appendix D. A complete copy of the revised manual is attached. l l

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6 9705050384 970428 l PDR ADOCK 05000309 R PDR

1 TABLE 1A l Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters,1996 Gaseous Effluents - Summation of All Releases Unit 1st 2nd Est. Total Quarten Quarter Error, % i l

A. Fission and Activation Gases l

Ci 1.60 E-01 4.12 E-03 2.50 E+01

1. Total release l
2. Average release rate for period pCi/sec 2.03 E-02 5.22 E-04
3. Percent of regulatory limit  % 4.70 E-04 1.61 E-06 I B. Iodines Ci 1.73 E-05 4.77 E-05 2.50 E+01 i l 1. Totallodine-131 l l 6.05 E-06
2. Average release rate for period Ci/sec .2.19 E-06 l
3. Percent of regulatory limit  % 9.61 E-06 2.65 E-05 .

i l C. Particulates l

1. Particulates with T-1/2 > 8 days Ci 7.49 E-06 N/D* 2.50 E+01 l
2. Average release rate for period pCi/sec 9.49 E-07 N/D*
3. Percent of regulatory limit  % 6.86 E-06 N/D*
4. Gross alpha radioactivity Ci 5.74 E-07 6.79 E-08 l D. Tritium Ci 9.85 E-01 3.27 E+00 2.50 E+01
1. Total release
2. Average release rate for period pCi/sec 1.25 E-01 4.14 E-01
3. Percent of regulatory limit  % 1.12 E-03 3.73 E-03 i i

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l N/D* = Not Detected 1 i

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. _ . _ _ . . . _ _ . . _ . . . _ _ _ - . _ . _ - _ _ . _ _ . . . . _ _ . . ~ _ . _ . . _ _ . . _ _ _ _ _ _ __

TABLElA Maine Yank'ee Atomic Power Station '

Effluent and Waste Disposal Annual Report Third and Fourth Quarters,1996 .

Gaseous Effluents - Summation of All Releases Unit 3rd 4th Est. Total  :

Quarter Quarter Error, %  :

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A. Fission and Activation Gases Ci 6.21 E+03 5.95 E+00 2.50 E+01

1. Total release pCi/sec 7.87 E-01 7.54 E-01
2. Average release rate for period

% 1.36 E-03 1.29 E-03

3. Percent of regulatory limit B. Iodines Ci 3.46 E-05 1.84 E-05 2.50 E+01
1. Total Iodine-131 Ci/sec 4.39 E-06 2.32 E-06
2. Average release rate for period
3. Percent of regulatory limit  % 1.93 E-05 1.02 E-05 C. Particulates
1. Particulates with T-1/2 > 8 days Ci 3.73 E-05 7.77 E-04 2.50 E+01 l 2. Average release rate for period pCi/sec 4.73 E-06 9.84 E-05
3. Percent ofregulatory limit  % 2.07 E-05 1.10 E-04
4. Gross alpha radioactivity Ci 2.34 E-07 1.36 E-07 D. Tritium .

Ci 4.13 E400 1.84 E+00 2.50 E+01

! 1. Total release

2. Average release rate for period pCi/sec 5.23 E-01 2.33 E-01

! 3. Percent of regulatory limit  % 4.71 E-03 2.10 E-03 t

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_ _ - . _ _ _ _ . _ - _ . . _ . . , , _ _ - _ ..__.. _ , - - - _ . .. l

TABLEIB Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters,1996 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode Unit 1st 2nd 1st 2nd Nuclides Released Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-85 Ci N/D* N/D* N/D* N/D*

Ci N/D* N/D* 5.02 E-03 N/D*

Krypton-85m Ci N/D* N/D* 4.07 E-03 N/D*

Krypton-87 Ci 'N/D

  • N/D* 8.98 E-03 N/D*

Krypton-88 Ci 1.54 E-05 2.33 E-04 5.41 E-02 3.44 E-03 Xenon-133 Ci 2.86 E-04 3.26 E-04 6.39 E-02 9.80 E-05 Xenon-135 Ci 2.03 E-05 8.57 E-06 2.70 E-03 N/D*

Xenon-135m Ci N/D* N/D* 2.32 E-03 N/D*

Xenon-138 Ci N/D* 1.30 E-05 2.21 E-03 N/D*

. Xenon-133m Ci N/D* N/D* 1.67 E-02 4.99 E-06 Argon-41 Ci N/D* N/D* N/D* N/D*

Xenon-131m Ci N/D* N/D* N/D* N/D*

Unidentified Ci 3.22 E-04 5.81 E-04 1.60 E-01 3.54 E-03 Total for period

2. Iodines Ci 1.73 E-05 4.77 E-05 N/D* N/D*

Iodine-131 Ci 5.67 E-05 2.82 E-04 N/D* 1.02 E-06 Iodine-133 Ci N/D* N/D* N/D* N/D*

Iodine-135 Total for period Ci 7.40 E-05 3.30 E-04 N/D* 1.02 E-06

3. Particulates Strontium-89 Ci N/D* N/D* N/D* N/D*

Strontium-90 Ci N/D* N/D* N/D* N/D*

Cesium-134 Ci N/D* N/D* N/D* N/D*

Cesium-137 Ci 5.87 E-06 N/D* N/D* N/D*

Barium Lanthanum-140 Ci N/D* N/D* N/D* N/D* _

Zinc-65 Ci N/D* N/D* N/D* N/D*

Cobalt-58 Ci N/D* N/D* N/D* N/D*

Cobalt-60 Ci 1.62 E-06 N/D* N/D* N/D*

Others- Ci N/D* N/D* N/D* N/D*

N/D* = Not Detected

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TABLEIB '

Maine Yankee Atomic Power Station i Efiluent and Waste Disposal Annual Report Third and Fourth Quarters,1996 l Gaseous Effluents - Elevated Release Continuous Mode Hatch Mode Unit 3rd 4th 3rd 4th Nuclides Released Quarter Quarter Quarter Quarter

1. Fission Gases Ci N/b* N/D* 2.27 E-01 8.23 E-01

< Kypton-85 Ci 4.87 E-06 4.41 E-04 N/D* 9.14 E-07 Krypton-85m Ci N/D* 3.60 E-04 N/D* N/D* f Krypton-87 Ci N/D* 1.90 E-04 N/D* N/D*

Krypton-88 Ci 1.26 E-03 3.38 E+00 5.76 E+00 1.62 E+00 Xenon-133 Ci 4.42 E-04 2.89 E-03 1.59 E-05 4.90 E-05 Xenon-135 Ci 2.39 E-05 4.18 E-04 N/D* N/D*

Xenon-135m Ci N/D* N/D* N/D* N/D*

Xenon-138 Ci N/D* N/D* 7.00 E-03 2.73 E-04 Xenon-133m Ci N/D* N/D* 4.24 E-06 3.45 E-06 )

Argon-41 Ci N/D* N/D* 2.17 E-01 1.22 E-01 Xenon-131m Ci N/D* N/D* N/D* N/D* ,

Unidentified  :

Ci 1.73 E-03 3.38 E+00 6.21 E+00 2.57 E+00 Total for period

2. Iodines Iodine-131 Ci 3.46 E-05 1.77 E-05 N/D* 1.44 E-08 Ci 7.90 E-05 N/D* N/D* N/D*

lodine-133 Ci N/D* N/D* N/D* N/D*

Iodine-135 Total for period Ci 1.14 E-04 1,77 E-05 N/D* 1.44 E-08

3. Particulates Strontium-89 Ci N/D* N/D* N/D* N/D*

Strontium-90 Ci N/D* N/D* N/D* N/D*

Cesium-134 Ci 1.37 E-08 8.93 E-06 N/D* N/D*

Cesium-137 Ci 3.73 E-05 2.21 E-05 N/D* N/D*

Barium-Lanthanum-140 Ci N/D* N/D* N/D* N/D* l Zinc-65 Ci N/D* N/D* N/D* N/D*

Cobalt-58 Ci 4.61 E-09 N/D* N/D* N/D*

Cobalt-60 Ci N/D* N/D* N/D* N/D*

Others- Cesium - 136** Ci N/D* 7.44 E-04 N/D* N/D* f l

    • = The presence of Cesium-136 was rechecked and verified. ,

N/D* = Not Detected l l

TABLEIC Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report January - December 1996**

Gaseous Effluents - Ground Level Release .

i Continuous Mode Nuclides Released Unit 4th '

Quarter

1. Fission Gases Krypton-85 Ci N/D*

Krypton-85m Ci N/D*

Krypton-87 Ci N/D* ,

Krypton-88 Ci N/D* l Ci 1.74 E-03 Xenon-133 Ci N/D* l Xenon-135 Xenon-135m Ci N/D* <

l Ci N/D*

Xenon-138 Ci 6.58 E-06 Xenon-133m Argon-41 Ci N/D* J Ci 4.17 E-05 Xenon-131m Unidentified Ci N/D*

Total for period Ci 1.79 E-03 l

l 2. Iodines lodine-131 Ci 6.47 E-07 Iodine-133 Ci N/D*

Iodine-135 Ci N/D*

Total for period Ci 6.47 E-07 l

3. Particulates Strontium-89 Ci N/D*

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l Strontium-90 Ci N/D*

Cesium-134 Ci 1.67 E-07 Cesium-137 Ci 1.52 E-06 Barium-Lanthanum-140 Ci N/D*

Zinc-65 Ci N/D*

Cobalt-58 Ci N/D*

Cobalt-60 Ci N/D*

! Others- Ci N/D*

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    • No ground level releases occurred during the first, second or third quarters. Only a continuous ground level release was made during the fourth quarter.  :

N/D* = Not Detected l

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TABLE 2A  ;

Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters,1996 l

i Liquid Effluents - Summation of All Releases Unit 1st Quarter 2nd Quarter Est. Total Error, %

A. Fission and Activation Products Total release (not including tritium, Ci 9.45 E-02 1.34 E-02 1.50 E+01

1. '

l gases, alpha) i pCi/ml 4.97 E-10 6.44 E-11

2. Avprage diluted concentration during penod Percent of applicable limit  % 1.25 E-02 1.87 E-03

( 3.

B. Tritium I Ci 3.14 E+01 2.03 E+01 1.50 E+01

1. Total Release 1 pCi/mi 1.65 E-07 9.77 E-08
2. Avgrage diluted concentration during penod Percent of applicable limit  % 1.65 E-02 9.77 E-03 3.

C. Dissolved and Entrained Gases Ci 1.78 E-03 1.30 E-03 1.50 E+01

1. Total Release pCi/mi 9.37 E-12 6.28 E-12
2. Avprage diluted concentration during penod Percent of applicable limit  % 4.68 E-06 3.14 E-06 3.

D. Gross Alpha Radioactivity Ci 1.98 E-06 3.56 E-07 1.50 E+01 l 1. Total release

2. Avgrage diluted concentration during pCi/ml 1.04 E-14 1.71 E-15 penod E. Volume of waste released (prior to liters 2.68 E+07 1.53 E+07 1.00 E+01 dilution)

F. Volume of dilutioh Water used during liters 1.90 E+11 2.08 E+11 1.00 E+01 period i

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i TABLE 2A Maine Yankee Atomic Power Station Ef0uent and Waste Disposal Annual Report Third and Fourth Quarters,1996 Liquid Effluents - Summation of All Releases Unit 3rd Quarter 4th Quarter Est. Total Error, % i A. Fission and Activation Products Total release (not including tritium, Ci 4.16 E-02 1.01 E-02 1.50 E+01 1.

gases, alpha) pCi/ml 2.65 E-10 5.67 E-11

2. Avprage diluted concentration during l

penod 1 Percent of applicable limit  % 4.49 E-03 1.40 E-03

! 3.

B. Tritium Ci 1.17 E+02 1.29 E+02 1.50 E+01

1. Total Release pCi/mi 7.46 E-07 7.24 E-07  ;

l 2. Avprage diluted concentration during penod Percent of applicable limit  % 7.46 E-02 7.24 E-02 3.

C. Dissolved and Entrained Gases Ci 1.12 E-02 1.54 E-01 1.50 E+01

1. Total Release Ci/ml 7.12 E-11 8.60 E-10
2. Avprage diluted concentration during penod Percent of applicable limit  % 3.56 E-05 4.31 E-04 3.

D. Gross Alpha Radioactivity Ci 1.25 E-07 4.63 E-07 1.50 E+01

1. Total release Avprage diluted concentration during pCi/ml 7.96 E-16 2.60 E-15 2.

penod E. Volume of waste released (prior to liters 3.66 E+07 3.16 E+07 1.00 E+01 dilution)

F. Volume of dilution water used during liters 1.57 E+11 1.78 E+11 1.00 E+01 period l

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TABLE 2B

  • Maine Yankee Atomic Power Station Effluent and Waste Dis sal AnnualReport First and Second uarters,1996 Liquid E uents Continuous Mode Batch Mode Unit 1st 2nd 1st 2nd Nuclides Released l Quarter Quarter Quarter Quarter 4

Strontium-89 Ci N/D* N/D* N/D* N/D*

Ci N/D* N/D* N/D* N/D*

Strontium-90 Ci 5.13 E-04 N/D* 4.79 E-05 6.35 E-06 Cesium-134 Ci 8.73 E-04 N/D* 7.35 E-04 4.60 E-04 Cesium-137 Ci N/D* N/D* N/D* N/D*

Iodine-131 Ci N/D* N/D* 1.15 E-03 1.60 E-04 Cobalt-58 i Ci 6.75 E-04 2.80 E-07 6.24 E-02 1.01 E-02 Cobalt-60 Ci N/D* N/D* N/D* N/D*

Iron-59 Ci N/D* N/D* N/D* N/D*

Zine-65 Ci N/D* N/D* 1.92 E-04 5.74 E-05 ]

Manganese-54 2.91 E-05 I Chr >mium-51 Ci N/D* N/D* 3.01 E-04 Ci N/D* N/D* N/D* 4.44 E-06 Zirconium-Niobium-95 Ci N/D* N/D* N/D* N/D* j j Molybdenum-99 Ci N/D* N/D* 4.49 E-06 1 I6 E-06 Technetium-99m Ci N/D* N/D* 5.39 E-06 3.69 E-05 Barium-Lanthanum-140 a

Ci N/D* N/D* N/D* N/D*

Cerium-141 N/D* N/D* 2.37 E-02 2,06 E-03 Others-Iron-55 Ci Iodine-133 Ci N/D* N/D* 3.52 E-06 N/D*

Antimony-125 Ci N/D* N/D* 3.74 E-03 4.65 E-04 Silver-110M Ci N/D* N/D* 8.07 E-05 3.04 E-05 Cobalt-57 Ci N/D* N/D* 7.49 E-06 1.91 E-06 Unidentified N/D* N/D* N/D* N/D*

Total for period (above) Ci 2.06 E-03 2.80 E-07 9.24 E-02 1.34 E-02 Xenon-133 Ci N/D* N/D* 1.67 E-03 1.27 E-03 Xenon-135 Ci N/D* N/D* 1.12 E-04 3.37 E-05 )

N/D* = Not Detected

- TABLE 2B Maine Yankee Atomic Power Station Effluent and Waste Dis sal Annual Report Third and Fourth uarters,1996 Liquid E uents Continuous Mode Batch Mode Unit 3rd 4th 3rd 4th Nuclides Released Quarter Quarter Quarter Quarter Ci N/D* N/D* N/D* N/D*

Strontium-89 Ci N/D* N/D* N/D* N/D*

Strontium-90 Ci N/D* 3.53 E-05 1.69 E-04 8.94 E-06 Cesium-134 Ci 2.15 E-04 1.37 E-04 2.39 E-03 2.13 E-04 Cesium-137 Ci N/D* 1.21 E-04 2.30 E-05 2.66 E-04 lodine-131 Ci 1.63 E-06 N/D* 2.25 E-03 6.04 E-04 Cobalt-58 Ci N/D* 1.14 E-05 9.98 E-03 2.61 E-03

Cob.1:-60 Ci N/D* N/D* 4.69 E-05 N/D*

Iron-59 Ci N/D* N/D* N/D* N/D*

Zinc-65 l N/D* 6.40 E-06 2.20 E-06 Manganese-54 Ci N/D*

Ci N/D* N/D* 7.62 E-04 3.86 E-04 Chromium-51 Ci N/D* N/D* 2.51 E-04 2.74 E-04 Zirconium-Niobium-95 Ci N/D* N/D* N/D* N/D*

Molybdenum-99 Ci N/D* N/D* 1.19 E-06 2.71 E-05

, Technetium-99m Ci N/D* N/D* 5.63 E-05 6.14 E-05 Barium-Lanthanum-140 Ci N/D* N/D* N/D* N/D*

Cerium-141 Ci N/D* N/D* 2.15 6-02 4.97 E-03 Others - Iron-55 Ci N/D* N/D* 3.27 E-06 N/D*

Antimony-124 Ci N/D* N/D* 8.22 E-04 9.53 E-05 Antimony-125 Ci N/D* N/D* 3.13 E-03 1.52 E-04 l Silver-110M Ci N/D* N/D* 1.00 E-05 N/D* l Ruthenium-105 Iodine-133 Ci N/D* 1.62 E-05 N/D* 3.73 E-06 Tellurium-132 Ci N/D* N/D* N/D* 2.51 E-06 Tin-113 Ci N/D* N/D* N/D* 1.39 E-06 Rhodium-105 Ci N/D* N/D* N/D* 1.94 E-05 Ci N/D* N/D* N/D* 4.82 E-05 Cadmium-109 Europium-155 Ci N/D* N/D* N/D* 5.08 E-06 Neptunium-237 Ci N/D* N/D* N/D* 1.38 E-05 N/D* N/D* N/D* N/D*

Unidentified Ci 2.17 E-04 3.21 E-04 4.14 E-02 9.76 E-03 Total for period (above)

Ci N/D* 2.98 E-04 1.08 E-02 1.49 E-01 Xenon-133 Ci N/D* N/D* 2.02 E-04 6.84 E-04 Xenon-135 l N/D* 1.91 E-05 1.42 E-04 2.67 E-03 Xenon-131m Ci Ci N/D* N/D* 2.46 E-05 1.14 E-03

~ Xenon-133m Xenon-135m Ci N/D* N/D* 8.97 E-06 N/D*

l Ci N/D* N/D* 2.09 E-06 1.29 E-05 Krypton-85m ,

N/U' = Not Detected

TABLE 3 Maine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Report First Half,1996 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel).

6-Month Est. Total Unit Period Error. %

1. Type of Waste.
a. Spend resins, filter sludges, etc. Cu.M. 12.8 Ci. 2.13 E+02 +/-25
b. Dry compressible waste, contaminated Cu.M. 19.2 Ci. 4.02 E+00 +/-25 equipment, DAW, Cement.
2. Estimate of major nuclide composition (by type of waste).
a. Co-60 53.55 % 1.14 E+02 Sb-125 20.14 % 4.29 E+01 Fe-55 17.76 % 3.78 E+01 C-14 5.34 % 1.14 E+0!

H-3 1.19 % 2.53 E+00 Ni-63 1.02 % 2.18 E+00

b. Co-60 34.76 % 1.40 E+00 Ni-63 26.63 % 1.07 E+00 Fe-55 25.45 % 1.02 E+00 Co-58 5.83 % 2.34 E-01 Cs-137 3.87 % 1.55 E-01 Cc-144 1.48 % 5.96 E-02 Cr-51 1.40% 5.64 E-02

TABLE 3 l (Continued)

3. Solid Waste Disposition Mode of Transportation Dgstination Number of Shinments Trucking over Highway Chem-Nuclear, Bamwell, SC 5

Trucking over Highway Scientific Ecology Group 2

(SEG), Oak Ridge, TN B. Irradiated Fuel Shipments (Disposition): None Shipped.

Additional ODCM Appendix C requirements.

Volume Est. Activity Solid Waste Class (Cu. M.) (Ci) Est. Total Error A 27.8 1.30 E+02 +/- 25%

B 0.5 3.09 E+00 +/- 25%

C 3.7 8.39 E+01 +/- 25%

Type Package Volume (Cu. M.)

Container Strong Tight Container 2.9 B-88 Strong Tight Container 38.3 Sealand High Integrity Container 5.5 RADLOC-195 High Integrity Container 0.5 NUHIC-55 High Integrity Container 3.7 EL-142 c l

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TABLE 3

Maine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Report Second Half,1996 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel).

6-Month Est. Total Unit Period Error. %

1. Type of Waste.
a. Spend resins, filter sludges, etc. Cu.M. 17.2 Ci. 1.71 E+02 +/-25 4 1

l

b. Dry compressible waste, contaminated Cu.M. 31.8 i l

Ci. 6.12 E+00 +/-25 equipment, DAW, Cement.

2. Estimate of major nuclide composition (by type of waste). I
a. Cs-137 37.53 % 6.42 E+01 Cs-134 18.75 % 3.21 E+01 Ni-63 17.39 % 2.98 E+01 Co-60 14.13 % 2.42 E+01 l Fe-55 10.18 % 1.74 E+01 l

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b. Co-60 33.80 % 2.07 E+00 J

Ni-63 25.81 % 1.58 E+00 Fe-55 24.65 % 1.51 E+00 Co-58 5.35 % 3.27 E-01 Cs-137 3.76 % 2.30 E-01 Ce-144 1.42 % 8.68 E-02 I

Cr-51 1.23 % 7.52 E-02 l

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TABLE 3 (Continued)

3. Solid Waste Disposition Number of Shipments Mode of Transnortation Destination Trucking over Highway Chem-Nuclear, Barnwell, SC 5

6 Trucking over Highway Scientific Ecology Group (SEG), Oak Ridge,TN 3 Trucking over Highway F.W. Hake Memphis, TM B. Irradiated Fuel Shipments (Disposition): None Shipped.

Additional ODCM Appendix C requirements.

Volume Est. Activity Solid Waste Class (Cu. M.) (Ci) Est. Total Error A 44.5 2.12 E+01 +/- 25%

B 4.5 1.56 E+02 +/- 25%

C 0.0 0.00 E+00 +/- 25%

Container Type Package Volume (Cu. M.)

Strong Tight Container 2.9 B-88 Sealand Strong Tight Container 38.3 Strong Tight Container 0.2 Steel Drum Steel Drum Strong Tight Container 0.3 RADLOC-195 High Integrity Container ,

5.5 NUHIC-120 High Integrity Container 4.5 EL-142 High Integrity Container 3.7 l

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TABLE 4 SunnlementalInformation

1. Reculatorv Limits Effluent Concentration
a. Fission and activation gases: 10CFR20; Appendix B, Table 2, Column 1
b. Iodines: 10CFR20; Appendix B, Table 2, Column I
c. Particulates,(with half lives greater than 8 days) 10CFR20; Appendix B, Table 2, Column 1
d. Liquid effluents: 10CFR20; Appendix B, Table 2, Column 2
e. Total noble gas concentration 2E-04 pCi/ml l
2. Average Energy - Not Apnlicable
3. Measurements and Anproximations of Radioactivity
a. Fission and Activation Gases Continuous Discharge - Vent stack samples are analyzed monthly. Activity levels determined are assumed constant for the surveillance interval. The continuous vent stack monitor reading is used as a basis for increasing periodic sample frequency.

Batch Discharges - Direct measurements of the waste gas hold-up drums are taken prior to discharge. Containment vents and purges are analyzed by direct measurement of the containment atmosphere at periodic intervals during discharge.

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b. lodmes Primary vent stack iodine totals are taken from a minimum of weekly measurements of an in-line charcoal filter.
c. Particulates Primary vent stack particulate totals are taken from a minimum of weekly measurements of an in-line particulate filter.

l l d. Liquid Effluents Samples of secondary systems' liquid effluents are analyzed weekly for gross alpha, tritium, l

j dissolved gases, and gamma emitting isotopes.

Each batch release is analyzed for gross alpha, tritium, dissolved gases, and gamma emitting isotopes prior to discharge.

Composite samples are made of secondary and primary system liquid effluents for a

! quarterly analysis of Strontium-90 and Strontium-89. Primary system liquid effluents are

! also analyzed quarterly for Iron-55.

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TABLE 4 l (Continued) l

4. Batch Releases
a. Liauids
1. Number of batch releases: 121
2. Total time period for batch releases: 2561 hours0.0296 days <br />0.711 hours <br />0.00423 weeks <br />9.744605e-4 months <br />,38 minutes
3. Maximum time period for a batch release: 612 hours0.00708 days <br />0.17 hours <br />0.00101 weeks <br />2.32866e-4 months <br />,0 minutes
4. Average time period for batch releases: 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />,10 minutes
5. Minimum time period for a batch release: 10 minutes
6. Average stream flow during periods of release of effluents into a flowing stream: N/A
7. Maximum gross release concentration ( Ci/ml): 4.23 E-07
b. Gaseous
1. Number of batch releases: 24
2. Total time period for batch releases: 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br />,33 minutes
3. Maximum time period for a batch release: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,50 minutes
4. Average time period for batch releases: I hours,19 minutes
5. Minimum time period for a batch release: 16 minutes
6. Maximum gross release rate (pCi/sec): 1.40 E+03
5. Unnlanned Releases
a. Liquid l

I There were no abnormal liquid releases during the reporting period.

b. Gaseous At approximately 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br /> on February 29,1996, while performing maintenance on valve CH-138 on the Volume Control Tank (VCT) level column, gas inadvertently escaped from the VCT into the Primary Auxiliary Building and discharged up the Primary ,

I Vent Stack. The duration of this release was approximately 30 minutes, and amounted to 0.16 Curies. The activity associated with this release is included in Tables l A and IB. j

6. On-Line Containment Purge l On-line containment purge was not utilized during 1996.

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APPENDIX A Radioactive Effluent Monitoring Instrumentation Reauirement: Radioactive effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Sections 2.3.3 and 2.3.4. With less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful, ODCM Sections 2.3.3 and 2.3.4 requires an explanation for the delay in correcting the i

inoperability in the next Annual Effluent Release Report.

Resnonse:

The Service Water monitor was declared inoperative on February 28,1995 afler the plant entered into an extended shutdown. This condition resulted from an absence of vacuum priming due to the shutdown conditions. Vacuum priming is required to supply sample to the monitor. Once vacuum priming was restored, it was i discovered that the sample pump was inoperable because of the mechanical l problems. The pump was subsequently repaired and the monitor was retumed to service on February 12,1996.

1 The Primary Vent Stack flow rate meter was declared inoperative on July 5,1995.

Delays were encountered in the repair of this stack mounted instrumentation due to unsafe conditions identified with the access ladder / platform. Once those conditions were repaired, the instrumentation was inspected and found to be  ;

obsolete, with the required repair parts no longer available. Receipt of a l replacement unit was delayed by a long procurement lead time. Upon receipt, the new instmment was installed, and the system retumed to service on September 13, 1996. The flow rate meter was subsequently again declared inoperative on November 19,1996 to fulfill an engineering requirement to perform a traverse of l

l the stack to verify the calibration of the unit. Completion of that activity was delayed when the vendor provided test equipment became inoperable. Pending completion of this requirement, the meter remained out of services for the remainder of the year.

l The Liquid Waste monitor was declared inoperative on January 6,1996 because of l

unexplained spiking during discharges. After inspection and testing, it was found l

that the spiking was the result of external conditions, and that the monitor was responding properly. The monitor was declared operable on February 23,1996.

Despite that, the remedial action required for an inoperative monitor continued until October 29,1996, when the external condition causing the spikes was corrected.

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APPENDIX B

! r Liauid Radwaste Treatment System l

I Requirement: With radioactive liquid waste being discharged without treatment with estimated doses in excess of the limits in ODCM Section 2.1.5, a report must be submitted to 4 the Commission in the Annual Effluent Release Report for the period. j l t Resoonse: The requirements of ODCM Section 2.1.5 were met during this period and,  :

therefore, no report is required.

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APPENDIX C Gaseous Radwaste Treatment System Reauirement: With radioactive gaseous waste being discharged without treatment with doses in excess of the limits in ODCM Section 2.2.6, a report must be submitted to the Commission in the Annual Effluent Release Report for the period.

Resnonse: The requirements of ODCM Section 2.2.6 were met during this period and, therefore, no report is required.

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APPENDIX D Lower Limit of Detection for Radiological Analyses l

Requirement: ODCM Section 2.5 requires that when unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.

Resnonse: All samples were counted in such a manner as to satisfy the specified a priori lower limits of detection.

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